The novel process enables designing of raw materials and processing parameters, enabling synergistic and simultaneous chemical reactions among the various reactants of the design mix of chemical precursor of brine sludge which includes barium sulphate, magnesium hydroxide, calcium carbonate, sodium chloride, silica, aluminum containing compounds necessary for developing highly efficient shielding phases leading to homogenous matrix of shielding materials.

The present invention provides a bidirectional energy-transfer system comprising: a thermally and/or electrically conductive concrete, disposed in a structural object; a location of energy supply or demand that is physically isolated from, but in thermodynamic and/or electromagnetic communication with, the thermally and/or electrically conductive concrete; and a means of transferring energy between the structural object and the location of energy supply or demand. The system can be a single node in a neural network. The thermally and/or electrically conductive concrete includes a conductive, shock-absorbing material, such as graphite. Preferred compositions are disclosed for the thermally and/or electrically conductive concrete. The bidirectional energy-transfer system may be present in a solar-energy collection system, a grade beam, an indoor radiant flooring system, a structural wall or ceiling, a bridge, a roadway, a driveway, a parking lot, a commercial aviation runway, a military runway, a grain silo, or pavers, for example.

A radiation shield unit, which shields against neutron rays, X-rays, and γ-rays, contains 10 vol % or more and 90 vol % or less of gadolinium.

A self-supporting inorganic and radiation-hard neutron shielding panel for use in absorbing thermal neutrons. The panel is constructed substantially of concrete and includes a high level of boron by weight to enhance the absorption of thermal neutrons. A layer of radiation-resistant fiber reinforcement within the panel enables production of a thin, strong panel that is self-supporting and easily transportable. Mounting means are included on the panel to facilitate easy mounting on a wall or similar surface. The panels are constructed entirely of inorganic materials and include at least 58% boron by weight to maximize their effectiveness in shielding against thermal neutrons. Further disclosed are methods for forming the neutron-shielding panels.

A radiation-shielding attenuation structure and method of forming the attenuation structure, wherein the attenuation structure is made by additively manufacturing a concrete material that includes one or more attenuation dopants configured to enhance the radiation shielding of the concrete material. The one or more attenuation dopants may be configured in the concrete material to attenuate one or more types of radiation, such as electromagnetic radiation, gamma radiation, X-ray radiation, or neutron radiation. The attenuation structure formed by the concrete material may be additively manufactured on-site according to a model that has already been pre-certified for safe or secure use, thereby providing a repeatable and reproducible process that can reduce lead times and fabrication costs. The attenuation structure may be easily modified during the additive manufacturing process to have different concrete mixtures with different attenuation characteristics, which increases the tailorability and flexibility in design of the attenuation structure.

Aspects of the present disclosure provide for cement, cement paste, cementitious paste, cementitious mortar, and concrete, methods of making cement, cement paste, cementitious paste, cementitious mortar, and concrete, structures incorporating the concrete, and the like, where the cement, cement paste, cementitious paste, cementitious mortar, and the concrete include elemental boron and/or one or more boron compounds (e.g., boron-doped cement, cement paste, cementitious paste, cementitious mortar, and concrete). The boron and/or a boron compound can be homogeneously distributed throughout the cement, cement paste, cementitious paste, cementitious mortar and/or concrete.

A neutron capture therapy system is provided, including a neutron generating device and a beam shaping assembly. The neutron capture therapy system further includes a concrete wall forming a space for accommodating the neutron generating device and the beam shaping assembly and shielding radiations generated by the neutron generating device and the beam shaping assembly. A support module is disposed in the concrete wall, the support module is capable of supporting the beam shaping assembly and is used to adjust the position of the beam shaping assembly, and the support module includes concrete and a reinforcing portion at least partially disposed in the concrete. The neutron capture therapy system designs a locally adjustable support for the beam shaping assembly, so that the beam shaping assembly can meet the precision requirement, improve the beam quality, and meet an assembly tolerance of the target.

The novel process enables designing of raw materials and processing parameters, enabling synergistic and simultaneous chemical reactions among the various reactants of the design mix of chemical precursor of brine sludge which includes barium sulphate, magnesium hydroxide, calcium carbonate, sodium chloride, silica, aluminum containing compounds necessary for developing highly efficient shielding phases leading to homogenous matrix of shielding materials.

The object of the invention relates to a neutron absorbing concrete wall (10), which concrete wall (10) has an internal delimiting surface (11a), and an external delimiting surface (11b) on an opposite side to the internal delimiting surface (11a), the essence of which is that it contains a first concrete layer (13a) on the side of the internal delimiting surface (11a), and a second concrete layer (13b) on the side of the external delimiting surface (11b), which first concrete layer (13a) contains at least 0.05 mass % boron-10 isotope (10B), and the second concrete layer (13b) is formed as heavyweight concrete. The object of the invention also relates to a method for creating a neutron radiation absorbing concrete wall (10) that has an internal delimiting surface (11a), and an external delimiting surface (11b) on an opposite side to the internal delimiting surface (11a), the essence of which is a first concrete layer (13a) containing at least 0.05 mass % boron-10 isotope (.sup.10B) is formed on the side of the internal delimiting surface (11a), and a second concrete layer (13b) created as heavyweight concrete is formed on the side of the external delimiting surface (11b). The object of the invention also relates to a neutron absorbing concrete wall (10), the essence of which is that it is formed as heavyweight concrete containing at least 0.05 mass % boron-10 isotope (.sup.10B).

The present invention provides a bidirectional energy-transfer system comprising: a thermally and/or electrically conductive concrete, disposed in a structural object; a location of energy supply or demand that is physically isolated from, but in thermodynamic and/or electromagnetic communication with, the thermally and/or electrically conductive concrete; and a means of transferring energy between the structural object and the location of energy supply or demand. The system can be a single node in a neural network. The thermally and/or electrically conductive concrete includes a conductive, shock-absorbing material, such as graphite. Preferred compositions are disclosed for the thermally and/or electrically conductive concrete. The bidirectional energy-transfer system may be present in a solar-energy collection system, a grade beam, an indoor radiant flooring system, a structural wall or ceiling, a bridge, a roadway, a driveway, a parking lot, a commercial aviation runway, a military runway, a grain silo, or pavers, for example.